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Category:E-Mail
MONTHYEARML24012A0492024-01-11011 January 2024 Request for Additional Information Regarding Final Response to Generic Letter 2004-02 ML23317A2012023-11-22022 November 2023 (External_Sender) Supplement - Byron Security Rule Exemption Request ISFSI Docket No. Reference ML23331A8922023-11-22022 November 2023 Supplement - Braidwood Security Rule Exemption Request ISFSI Docket No. Reference ML23321A2012023-11-17017 November 2023 NRR E-mail Capture - Constellation Energy Generation, LLC - Fleet Request - Acceptance of Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds (L-2023-LLR-0062) ML23312A1302023-11-0707 November 2023 Final Rci/Rai - Constellation R. E. Ginna Nuclear Power Plant - Exemption from Security Rule (EPID L-2023-LLE-0029) (Email) ML23311A1682023-11-0707 November 2023 NRR E-mail Capture - Constellation - Fleet Request - Acceptance of Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections (L-2023-LLR-0053 and L-2023-LLR-005 ML23311A1692023-11-0707 November 2023 NRR E-mail Capture - Constellation - Fleet Request - Acceptance of Proposed Alternative for Examinations of Exam Categories B-B, B-D, and C-A SG Pressure Retaining Welds and Full Penetration Welded Nozzles (L-2023-LLR-0055 and L-2023-LLR-00 ML23305A2992023-11-0101 November 2023 NRR E-mail Capture - NRC Acceptance Review of Byron, Unit 2, Relief Request I4R-24 ML23304A0222023-10-30030 October 2023 NRR E-mail Capture - Final RCI - Constellation Energy Generation, LLC - Braidwood 1 & 2 - Exemption from Security Rule (L-2023-LLE-0030) ML23304A0202023-10-30030 October 2023 NRR E-mail Capture - Final RCI - Constellation Energy Generation, LLC - Byron 1 & 2 - Exemption from Security Rule (L-2023-LLE-0027) ML23304A0152023-10-30030 October 2023 NRR E-mail Capture - Final RCI - Constellation Energy Generation, LLC - Calvert Cliffs 1 & 2 - Exemption from Security Rule (L-2023-LLE-0033) ML23272A0602023-09-29029 September 2023 NRR E-mail Capture - NRC Acceptance Review of Byron, Unit 1, Relief Request I4R-25 ML23187A0092023-07-0606 July 2023 NRR E-mail Capture - NRC Acceptance Review of Byron and Braidwood Request to Adopt TSTF-370 ML23181A0732023-06-30030 June 2023 NRR E-mail Capture - Acceptance Review for Calvert Cliffs TSTF-59A ML23160A0222023-06-0606 June 2023 NRR E-mail Capture - Calvert Cliffs - Long Term Coupon Surveillance Program RAI ML23156A0102023-06-0404 June 2023 NRR E-mail Capture - Calvert Cliffs - RAI License Amendment Request for Emergency Desiel Generator ML23103A4692023-04-12012 April 2023 NRR E-mail Capture - NRC Acceptance Review of Braidwood Request for Amendment to Revise TS 3.7.9 ML23080A1002023-03-21021 March 2023 NRR E-mail Capture - Acceptance Review for Calvert Cliffs Repair Replacement of Saltwater System Buried Piping ML23080A0672023-03-21021 March 2023 NRR E-mail Capture - Acceptance Review for Calvert Cliffs Unit 1 - LAR to Modify the Long-Term Coupon Surveillance Program ML23069A0332023-03-0606 March 2023 Email to K. Lueshen Byron and Braidwood Commitment 10 - Request for Additional Information Set 1 ML23026A1332023-01-26026 January 2023 NRR E-mail Capture - Acceptance Review for Calvert Cliffs Deletion of License Condition for Decommissioning Trust LAR ML23115A2412023-01-20020 January 2023 NRR E-mail Capture - Preliminary RAIs Related to L-2022-LLA-0131 - Byron, Unit 2, Reinsertion of an Accident Tolerant Fuel Lead Test Assembly ML22354A2622022-12-20020 December 2022 NRR E-mail Capture - Constellation Energy Generation, LLC - Fleet Request - Acceptance of Request to Use Certain Provisions of the 2019 Edition of the ASME BPV Code, Section XI ML22342B1462022-11-21021 November 2022 NRR E-mail Capture - Acceptance Review for TSTF 295A ML22325A0052022-11-18018 November 2022 NRR E-mail Capture - Constellation Energy Generation, LLC - Fleet Request - Acceptance of License Amendment Request to Adopt TSTF-273-A, Revision 2 ML22284A1022022-10-0606 October 2022 NRR E-mail Capture - NRC Acceptance Review for Byron, Unit 2, License Amendment Request (LAR) to Reinsert an Accident Tolerant Fuel (ATF) Lead Test Assembly (LTA) (L-2022-LLA-0131) ML22339A0032022-09-28028 September 2022 R. E. Ginna Nuclear Power Plant - Ginna: Acceptance Review: to Revise Technical Specifications (TS) TS 5.6.5, Core Operating Limits Report ML22269A4522022-09-22022 September 2022 R. E. Ginna Nuclear Power Plant - Acceptance Review: to Revise Technical Specifications (TS) TS 5.6.5, Core Operating Limits Report (COLR) NRC-2100-2022, EN 55999 Valcor Coil Shell Assemblies Final Notification (004)2022-09-12012 September 2022 EN 55999 Valcor Coil Shell Assemblies Final Notification (004) ML22255A0132022-09-0909 September 2022 NRR E-mail Capture - NRC Acceptance Review of Braidwood, Byron, Calvert Cliffs, Ginna - License Amendment Request to Adopt TSTF-577 ML22200A0782022-07-19019 July 2022 NRR E-mail Capture - Constellation Energy Generation, LLC - Fleet Request to Use Honeywell Mururoa V4F1 R Supplied Air Suits NRC 2110-2022, EN 55999 - Valcor Engineering Corporation (009)2022-07-18018 July 2022 EN 55999 - Valcor Engineering Corporation (009) ML22189A0602022-07-0707 July 2022 NRR E-mail Capture - Draft RAI for Byron/Braidwood TSTF-501 ML22136A2722022-05-16016 May 2022 NRR E-mail Capture - NRC Acceptance Review of Braidwood and Byron Adoption of TSTF-501 ML22138A1672022-05-16016 May 2022 R. E. Ginna Nuclear Power Plant - Acceptance Review TS to Revise Technical Specifications (TS) for the Spent Fuel Pool Charcoal System and Two (2) TS Administrative Changes (EPID-L-2022-LLA-0057) ML22271A0772022-05-0606 May 2022 NRR E-mail Capture - Final RAIs 9.1.2021 Constellation Relief Request ML22129A0132022-05-0606 May 2022 NRR E-mail Capture - Draft RAIs for Requests for Alternatives I4R-17, I4R-23, ISI-05-018, I6R-10 ML22116A0242022-04-25025 April 2022 NRR E-mail Capture - NRC Acceptance Review of Braidwood, Byron, and Ginna Request to Adopt TSTF-246 ML22105A0722022-04-15015 April 2022 NRR E-mail Capture - Braidwood/Byron Verbal Authorization for Proposed Alternative I4R-15/I4R-21 ML22091A0852022-04-0101 April 2022 NRR E-mail Capture - Braidwood and Byron - Final RAI Regarding Proposed Alternative for Various Pressurizer Welds (EPID L-2021-LLR-0035 and 0036) ML22091A2392022-04-0101 April 2022 NRR E-mail Capture - Calvert Cliffs - Formal RAI for Proposed Alternative for Examinations of Certain Pressurizer Welds ML22091A2402022-03-23023 March 2022 NRR E-mail Capture - (External_Sender) Salem Generating STATION-INCIDENTAL Take of Atlantic Sturgeon Collected on 03/22/2022 ML22075A1912022-03-16016 March 2022 NRR E-mail Capture - Acceptance for Review of Proposed Alternative Repair Method for Buried Class 3 Saltwater System Piping ML22088A1562022-03-0202 March 2022 NRR E-mail Capture - Byron, Braidwood, Calvert Cliffs, and Ginna - Non-acceptance of Application to Revise Technical Specifications 5.6.5.b, the Core Operating Limits Report (COLR) ML22059B0602022-02-28028 February 2022 Change to Review Schedule Regarding Proposed Alternative for Various Pressurizer Welds ML22091A0842022-02-24024 February 2022 NRR E-mail Capture - Braidwood and Byron - Withdrawal of Draft RAI Regarding Proposed Alternative for Various Pressurizer Welds (EPID L-2021-LLR-0035 and 0036) ML22060A0172022-02-23023 February 2022 NRR E-mail Capture - Calvert Cliffs Nuclear Power Plant, Units 1 and 2 - Withdraw of Draft RAI Regarding Proposed Alternative for Various Pressurizer Welds ML22041B5362022-02-10010 February 2022 NRR E-mail Capture - Constellation Energy Generation, LLC - Request for Additional Information Regarding Fleet License Amendment Request to Adopt TSTF-541 ML21281A1402022-01-14014 January 2022 Acceptance for Review of Proposed Alternative ISI-05-018 for Examinations of Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles ML23089A0152022-01-0505 January 2022 NRR E-mail Capture - NRC Acceptance Review of Byron - Proposed Alternative for Examinations of Categories B-B, B-D, and C-A SG Welds and Nozzles 2024-01-11
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24012A0492024-01-11011 January 2024 Request for Additional Information Regarding Final Response to Generic Letter 2004-02 ML23339A0452023-12-0505 December 2023 Request for Information for an NRC Post-Approval Site Inspection for License Renewal Inspection Report 05000546/2024010 ML23312A1302023-11-0707 November 2023 Final Rci/Rai - Constellation R. E. Ginna Nuclear Power Plant - Exemption from Security Rule (EPID L-2023-LLE-0029) (Email) ML23297A2352023-10-26026 October 2023 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection ML23219A1662023-08-16016 August 2023 Request for Additional Information Regarding Proposed Alternative to the Requirements for Repair/Replacement of Saltwater (SW) System Buried Piping (EPID: L-2023-LLR-0006) - Non-proprietary ML23209A7242023-07-31031 July 2023 Request for Information on the NRC Quadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000454/2024010 and 05000455/2024010 ML23198A0372023-07-17017 July 2023 Information Request to Support Upcoming Problem Identification and Resolution (PIR) Inspection at Byron Nuclear Plant ML23191A8442023-07-10010 July 2023 05000456; 05000457 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML23172A1172023-06-22022 June 2023 Notification of NRC Fire Protection Team Inspection Request for Information ML23160A0222023-06-0606 June 2023 NRR E-mail Capture - Calvert Cliffs - Long Term Coupon Surveillance Program RAI ML23156A0102023-06-0404 June 2023 NRR E-mail Capture - Calvert Cliffs - RAI License Amendment Request for Emergency Desiel Generator ML23110A3202023-04-21021 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML23094A1352023-04-0404 April 2023 Request for Information for Nrc Commercial Grade Dedication Inspection Inspection Report 05000456/2023010 05000457/2023010 ML23069A0332023-03-0606 March 2023 Email to K. Lueshen Byron and Braidwood Commitment 10 - Request for Additional Information Set 1 ML23069A0342023-03-0606 March 2023 Unit 1 Lr Commitment 10 RAI Set 1 - (Non-Proprietary) ML23115A2412023-01-20020 January 2023 NRR E-mail Capture - Preliminary RAIs Related to L-2022-LLA-0131 - Byron, Unit 2, Reinsertion of an Accident Tolerant Fuel Lead Test Assembly ML23018A1632023-01-18018 January 2023 Notification of NRC Baseline Inspection and Request for Information ML22241A0522022-08-29029 August 2022 Notification of NRC Baseline Inspection and Request for Information Inspection Report 05000456/2022004 05000457/2022004 ML22237A0272022-08-25025 August 2022 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML22179A2112022-06-28028 June 2022 Notification of Conduct of a Fire Protection Team Inspection ML22160A3962022-06-0909 June 2022 R. E. Ginna Nuclear Power Plant, LLC - Request for Information for a Biennial Problem Identification and Resolution Inspection; Inspection Report 05000244/2022010 ML22271A0772022-05-0606 May 2022 NRR E-mail Capture - Final RAIs 9.1.2021 Constellation Relief Request ML22129A0132022-05-0606 May 2022 NRR E-mail Capture - Draft RAIs for Requests for Alternatives I4R-17, I4R-23, ISI-05-018, I6R-10 ML22116A1272022-04-26026 April 2022 Unit 2 RFI for an NRC Triennial Heat Exchanger/Sink Performance Inspection and RFI IR 05000454/2022002 05000455/2022002 ML22091A2392022-04-0101 April 2022 NRR E-mail Capture - Calvert Cliffs - Formal RAI for Proposed Alternative for Examinations of Certain Pressurizer Welds ML22091A0852022-04-0101 April 2022 NRR E-mail Capture - Braidwood and Byron - Final RAI Regarding Proposed Alternative for Various Pressurizer Welds (EPID L-2021-LLR-0035 and 0036) ML22041B5362022-02-10010 February 2022 NRR E-mail Capture - Constellation Energy Generation, LLC - Request for Additional Information Regarding Fleet License Amendment Request to Adopt TSTF-541 ML22034A9862022-02-0404 February 2022 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000456/2022402 05000457/2022402 ML21350A4372021-12-16016 December 2021 Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team) Inspection Report 05000456/2022010 and 05000457/2022010 ML21308A5592021-11-0404 November 2021 NRR E-mail Capture - NRC Request for Additional Information for Ginna Biennial EP Exercise Exemption Request ML21287A0322021-10-13013 October 2021 Request for Additional Information Re Proposed Alternative for Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds ML21287A0932021-10-0505 October 2021 Request for Additional Information: Calvert Cliffs 1 & 2 LAR to Revise Spent Fuel Pool Cooling - Shutdown Cooling Systems Licensing Basis (EPID L-2021-LLA-0112) (Email) ML21273A3312021-10-0404 October 2021 Information Request to Support Upcoming Biennial Problem Identification and Resolution (Pi&R) Inspection at Byron Station ML21256A1902021-09-10010 September 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21228A2352021-08-17017 August 2021 Notification of NRC Baseline Inspection and Request for Information Inspection Report 05000457/2021004 ML21187A2232021-07-29029 July 2021 Temporary Instruction 2515/194 Inspection Documentation Request ML21203A3112021-07-21021 July 2021 NRR E-mail Capture - Final Byron Permanently Defueled Technical Specifications (PDTS) - Second Round RAI ML21193A0942021-07-12012 July 2021 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML21189A1602021-07-0808 July 2021 NRR E-mail Capture - Request for Additional Information - Braidwood, Byron, and Ginna - Amendment to Address the Issues in Westinghouse NSALs ML21189A1612021-07-0808 July 2021 NRR E-mail Capture - Second Round Request for Additional Information - Byron Permanently Defueled Technical Specification Amendment ML21180A1562021-06-28028 June 2021 Request for Additional Information Regarding License Amendment Request Concerning Containment Sump ML21144A2132021-05-24024 May 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21130A0382021-05-21021 May 2021 Memo to File - Draft Request for Additional Information Relief Request CISI-03-01 Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements ML21117A0342021-05-0505 May 2021 Request for Additional Information Regarding Proposed Alternative to Use ASME Code Case N-893 ML21119A1082021-04-27027 April 2021 Ti 2515/194 Inspection Documentation Request ML21076A5152021-03-17017 March 2021 R. E. Ginna Nuclear Power Plant - RAI Steam Generator LAR to Revise Technical Specifications for Steam Generator Tube Inspection Frequency (EPID L-2020-LLA-0207) (e-mail) ML21062A0652021-03-0101 March 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative to Documentation Requirements for Pressure Retaining Bolting ML21057A1022021-02-25025 February 2021 Notification of NRC Fire Protection Team Inspection Request for Information; Inspection Report 05000456/2021010; 05000457/2021010 ML21053A3142021-02-22022 February 2021 Information Request for a Triennial Baseline Design Bases Assurance Inspection (Team); Inspection Report 05000317/2021010 and 05000318/2021010 ML21049A2572021-02-18018 February 2021 Request for Additional Information Byron/Dresden Proposed Changes to Site Emergency Plans to Support Post-Shutdown and Permanently Defueled Conditions (EPID-2020-LLA-0240 & EPID-2020-LLA-0237) 2024-01-11
[Table view] |
Text
From: Purnell, Blake Sent: Friday, January 29, 2021 12:55 PM To: Loomis, Thomas R:(GenCo-Nuc) (thomas.loomis@exeloncorp.com)
Cc: Salgado, Nancy; Gudger, David T:(GenCo-Nuc)
Subject:
Exelon Generation Company, LLC - Request for Additional Information Regarding Fleet Alternative Request to Use ASME Code Case N-885 Attachments: RAI - Exelon RR N-885.pdf Mr. Loomis, By application dated April 28, 2020 (Agencywide Documents Access and Management System Accession No. ML20119B061), Exelon Generation Company, LLC (Exelon) submitted a request in accordance with Paragraph 50.55a(z)(2) of Title 10 of the Code of Federal Regulations (10 CFR) for a proposed alternative to certain requirements of 10 CFR 50.55a at Braidwood Station, Units 1 and 2; Byron Station, Unit Nos. 1 and 2; Calvert Cliffs Nuclear Power Plant, Units 1 and 2; and R. E. Ginna Nuclear Power Plant. The proposed alternative would allow Exelon to use the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-885, Alternative Requirements for Table IWB 2500-1, Examination Category B-N-1, Interior of Reactor Vessel, Category B-N-2, Welded Core Support Structures and Interior Attachments to Reactor Vessels, Category B-N-3, Removable Core Support Structures: Section XI, Division 1, at these facilities.
The U.S. Nuclear Regulatory Commission staff is reviewing the application and has determined that additional information is needed to complete the review. A response to the attached request for additional information is requested to be provided within 30 days from the date of this email. If you have any questions, please contact me by email or phone at (301) 415-1380.
Sincerely, Blake Purnell, Project Manager Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Docket Nos. STN 50-456, STN 50-457, STN 50-454, STN 50-455, 50-317, 50-318, and 50-244 EPID L-2020-LLR-0069 OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/BC NAME BPurnell NSalgado DATE 1/29/21 1/26/21
Hearing Identifier: NRR_DRMA Email Number: 990 Mail Envelope Properties (BLAPR09MB64814CC8DC7ADD5C73CAB2B5E6B99)
Subject:
Exelon Generation Company, LLC - Request for Additional Information Regarding Fleet Alternative Request to Use ASME Code Case N-885 Sent Date: 1/29/2021 12:54:41 PM Received Date: 1/29/2021 12:54:41 PM From: Purnell, Blake Created By: Blake.Purnell@nrc.gov Recipients:
"Salgado, Nancy" <Nancy.Salgado@nrc.gov>
Tracking Status: None "Gudger, David T:(GenCo-Nuc)" <David.Gudger@exeloncorp.com>
Tracking Status: None "Loomis, Thomas R:(GenCo-Nuc) (thomas.loomis@exeloncorp.com)" <thomas.loomis@exeloncorp.com>
Tracking Status: None Post Office: BLAPR09MB6481.namprd09.prod.outlook.com Files Size Date & Time MESSAGE 1748 1/29/2021 12:54:41 PM RAI - Exelon RR N-885.pdf 126067 Options Priority: Normal Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
REQUEST FOR ADDITIONAL INFORMATION EXELON GENERATION COMPANY, LLC PROPOSED ALTERNATIVE TO USE ASME CODE CASE N-885 DOCKET NOS. STN 50-456, STN 50-457, STN 50-454, STN 50-455, 50-317, 50-318, AND 50-244 By application dated April 28, 2020 (Agencywide Documents Access and Management System Accession No. ML20119B061), Exelon Generation Company, LLC (Exelon) submitted a request in accordance with Paragraph 50.55a(z)(2) of Title 10 of the Code of Federal Regulations (10 CFR) for a proposed alternative to certain requirements of 10 CFR 50.55a at Braidwood Station, Units 1 and 2 (Braidwood); Byron Station, Unit Nos. 1 and 2 (Byron); Calvert Cliffs Nuclear Power Plant, Units 1 and 2 (Calvert Cliffs); and R. E. Ginna Nuclear Power Plant (Ginna). The proposed alternative would allow Exelon to use the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (BPV) Code Case N-885, Alternative Requirements for Table IWB-2500-1, Examination Category B-N-1, Interior of Reactor Vessel, Category B-N-2, Welded Core Support Structures and Interior Attachments to Reactor Vessels, Category B-N-3, Removable Core Support Structures: Section XI, Division 1, at these facilities.
The regulations in 10 CFR 50.55a(z) state, in part, that alternatives to the requirements in paragraphs (b) through (h) of 10 CFR 50.55a may be authorized by the NRC if the licensee demonstrates that: (1) the proposed alternative provides an acceptable level of quality and safety, or (2) compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
The U.S. Nuclear Regulatory Commission (NRC) has reviewed the application and determined that the information below is needed to complete its review.
Request for Additional Information (RAI) 1 Discussion The April 28, 2020, application states, in part (emphasis added):
Exelon proposes to implement the requirements of ASME Code Case N-885 in lieu of the requirements of Section XI, IWB-2500(a), Table IWB-2500-1 (B-N-1, B-N-2, B-N-3), and IWB-3520. The Code Case has eliminated Table IWB-2500-1 (B-N-1, B-N-2, B-N-3), Item Number B13.10 VT-3 examinations and associated acceptance standards. The current code technical requirements concerning Examination Category B-N-2 and B-N-3, Item Numbers B13.50, B13.60, and B13.70 examinations and associated acceptance standards are retained but with modified Examination Category and Item Number assignments.
Currently, the acceptance standard for VT-3 visual examinations of interior attachments beyond the beltline region (Item No. B13.60, Examination Category B-N-2) and core support structure (Item No. B13.70, Examination Category B-N-3) are specified in subparagraph IWB-3520.2 of the ASME BPV Code, Section XI, which states:
The following relevant conditions28 shall require corrective action in meeting the requirements of IWB-3122 prior to service or IWB-3142 prior to continued service:
(a) structural distortion or displacement of parts to the extent that component function may be impaired; (b) loose, missing, cracked, or fractured parts, bolting, or fasteners; (c) foreign materials or accumulation of corrosion products that could interfere with control rod motion or could result in blockage of coolant flow through fuel; (d) corrosion or erosion that reduces the nominal section thickness by more than 5%;
(e) wear of mating surfaces that may lead to loss of function; or (f) structural degradation of interior attachments such that the original cross-sectional area is reduced more than 5%.
Subparagraphs IWB-3122.1 and IWB-3142.1 state, in part, that components whose visual examination confirms the absence of the relevant conditions shall be acceptable for service or continued service, respectively.
Code Case N-885 would require VT-3 visual examinations of interior welded attachments beyond the beltline region, welded core support structure, and removable core support structure (referred to as the subject components below). Code Case N-885 provides an alternative acceptance standard (-3520.2) for the VT-3 visual examinations of these components that does not include condition (c) above.
Exelons statement that the associated acceptance standards are retained appears to be inconsistent with the changes to the acceptance standard for VT-3 visual examinations in Code Case N-885. In addition, the application has not provided a basis for using this alternative acceptance standard (-3520.2). The application cites EPRI report 3002012966, Evaluation of Basis for Periodic Visual Examination of Accessible Areas of Reactor Vessel Interior per Examination Category B-N-1 of ASME Section XI, Division 1, as the primary basis for the proposed alternative. However, changes to the requirements for Examination Categories B-N-2 and B-N-3 were not within the scope of this EPRI report.
Request With respect to the components subject to VT-3 visual examinations under Code Case N-885, demonstrate that either:
A. the proposed alternative acceptance standard (-3520.2) for VT-3 visual examinations in Code Case N-885 provides an acceptable level of quality and safety, or B. compliance with subparagraph IWB-3520.2 of the ASME BPV Code, Section XI, would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
RAI 2
Discussion The licensee requested, in part, an alternative to the acceptance standard for VT-3 visual examinations in subparagraph IWB-3520.2 of the ASME BPV Code, Section XI. Code Case N-885 eliminates the subparagraph IWB-3520.2 requirement to perform corrective action if foreign materials or accumulation of corrosion products that could interfere with control rod motion or could result in blockage of coolant flow through fuel (condition (c) above) are identified during the VT-3 visual examinations of the subject components.
The application does not discuss how related regulatory requirements would continue to be met with this proposed change. For example, the licensee proposes changes to specific corrective action requirements in the ASME BPV Code, Section XI, but the application does not discuss the more general corrective action requirements in Criterion XVI, Corrective Action, of 10 CFR Part 50, Appendix B. In addition, the technical specifications for each facility include requirements regarding control rods, reactor fuel, and the emergency core cooling system that may apply upon discovery of condition (c).
Request Describe how other regulatory requirements would continue to ensure that control rod motion and coolant flow through reactor fuel is acceptable. Discuss how these regulatory requirements would continue to be met with the proposed change in the acceptance standard for VT-3 visual examinations. The discussion should include the following regulatory requirements:
x Criterion XVI of 10 CFR Part 50, Appendix B, and x Technical specification requirements (e.g., operability definition, limiting conditions for operations, surveillance requirements) related to control rods, reactor fuel, and the emergency core cooling system.
RAI 3
The application states, in part:
The proposed alternative is for use of Code Case N-885 for the remainder of each plants 10-year inspection interval as specified in Section 2 or such time as the NRC approves the Code Case in the Regulatory Guide or other document.
This statement does not clearly indicate that Exelon would discontinue use of the proposed alternative at the end of the current 10-year inservice inspection interval for each plant if the NRC has not approved the Code Case N-885 for generic use.
Confirm that the duration of the proposed alternative would not go beyond the current 10-year inservice inspection interval for each plant.